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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217F8231999-10-13013 October 1999 Informs That on 990930,NRC Completed mid-cycle PPR of Catawba Nuclear Station.Based on Review,Nrc Did Not Identify Any New Areas That Warranted More than Core Insp Program Over Next Five Months.Historical Listing of Issues,Encl ML20217H0041999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML20217F1301999-10-0707 October 1999 Forwards Rev 1 to Request for Relief 99-03 from Requirements of ASME B&PV Code,In Order to Seek Relief from Performing Individual Valve Testing for Certain Valves in DG Starting (Vg) Sys ML20212J3011999-10-0101 October 1999 Forwards Exemption from Certain Requirements of 10CFR54.17(c) Re Schedule for Submitting Application for Operating License Renewal.Se Also Encl ML20217K2651999-10-0101 October 1999 Forwards Retake Exams Repts 50-413/99-302 & 50-414/99-302 on 990921-23.Two of Three ROs & One SRO Who Received Administrative Section of Exam Passed Retake Exam, Representing 75 Percent Pass Rate 05000414/LER-1999-004, Forwards LER 99-004-01,providing Correction to Info Previously Provided in Rev 0 of Rept.Planned Corrective Actions Contain Commitments1999-09-27027 September 1999 Forwards LER 99-004-01,providing Correction to Info Previously Provided in Rev 0 of Rept.Planned Corrective Actions Contain Commitments 05000413/LER-1999-015, Forwards LER 99-015-00 Re Inoperability of Auxiliary Bldg Ventilation Sys That Exceeded TS Limits Due to Improperly Positioned Vortex Damper.Commitments Are Contained in Corrective Actions Section of Encl Rept1999-09-27027 September 1999 Forwards LER 99-015-00 Re Inoperability of Auxiliary Bldg Ventilation Sys That Exceeded TS Limits Due to Improperly Positioned Vortex Damper.Commitments Are Contained in Corrective Actions Section of Encl Rept ML20217A7911999-09-24024 September 1999 Forwards Insp Repts 50-413/99-05 & 50-414/99-05 on 990718- 0828 at Catawba Facility.Nine NCVs Identified Involving Inadequate Corrective Actions Associated with Degraded Svc Water Supply Piping to Auxiliary Feedwater Sys ML20212E6471999-09-24024 September 1999 Discusses GL 98-01 Issued by NRC on 980511 & DPC Responses for Catawba NPP & 990615.Informs That NRC Reviewed Response for Catawba & Concluded That All Requested Info Provided.Considers GL 98-01 to Be Closed for Catawba ML20212F0941999-09-21021 September 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals for Cns,Units 1 & 2 ML20212M2001999-09-20020 September 1999 Confirms 990913 Telcon Between M Purser & R Carroll Re Management Meeting to Be Conducted on 991026 in Atlanta,Ga to Discuss Operator Licensing Issues 05000414/LER-1999-005, Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments1999-09-20020 September 1999 Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments ML20212D5321999-09-15015 September 1999 Informs That Duke Energy Corp Agrees to Restrict Max Fuel Rod Average Burnup to 60,000 Mwd/Mtu,In Order to Support NRC Final Approval & Issuance of Requested Amend ML20212B4641999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for Catawba Nuclear Station,Units 1 & 2 ML20212A4131999-09-14014 September 1999 Informs That TR DPC-NE-2009P Submitted in 990817 Affidavit, Marked Proprietary,Will Be Withheld from Public Disclosure, Pursuant to 10CFR2.709(b) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20212M1931999-09-13013 September 1999 Refers to 990909 Meeting Conducted at Region II Office Re Presentation of Licensee self-assessment of Catawba Nuclear Station Performance.List of Attendees & Licensee Presentation Handout Encl ML20212A3751999-09-10010 September 1999 Informs That Postponing Implementation of New Conditions Improved by RG 1.147,rev 12,acceptable Since Evaluation on Relief Based on Implementation Code Case for Duration of Insp Interval ML20212A5191999-09-0808 September 1999 Requests NRC Approval for Relief from Requirements of ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,App VI,VI-2430(c) & 2440(b).Approval of 99-GO-002 Is Requested by 000301 05000413/LER-1999-014, Forwards LER 99-014-00, Missed Surveillance & Operation Prohibited by TS Occurred as Result of Defective Procedures or Program & Inappropriate TS Requirements. Planned Corrective Action Stated in Rept Represents Commitment1999-09-0101 September 1999 Forwards LER 99-014-00, Missed Surveillance & Operation Prohibited by TS Occurred as Result of Defective Procedures or Program & Inappropriate TS Requirements. Planned Corrective Action Stated in Rept Represents Commitment 05000414/LER-1999-003, Forwards LER 99-003-01, Unplanned Actuation of ESFAS Due to a SG High Level Caused by Inadequate Procedural Guidance. Suppl Rept Provides Info Re Root Cause & Corrective Actions Associated with Event Developed Subsequent to Rev1999-08-31031 August 1999 Forwards LER 99-003-01, Unplanned Actuation of ESFAS Due to a SG High Level Caused by Inadequate Procedural Guidance. Suppl Rept Provides Info Re Root Cause & Corrective Actions Associated with Event Developed Subsequent to Rev 0 of LER ML20211H1741999-08-30030 August 1999 Forwards Comments on Catawba Nuclear Station Units 1 & 2 & McGuire Nuclear Station,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid.Ltr Dtd 990107,rept ATI-98-012-T005 & Partial marked-up Rept WCAP-14995 Encl ML20211M4451999-08-30030 August 1999 Forwards Summary of Util Conclusions Re Outstanding Compliance Issue Re Staff Interpretation of TS SR 3.0.1,per Insp Repts 50-369/99-03 & 50-370/99-03,as Discussed with NRC During 990618 Meeting 05000413/LER-1999-013, Forwards LER 99-013-00,re RHR Heat Exchanger Bypass Valves Not Verified Per TS Surveillance.Surveillance Procedures Have Been Revised & There Are No Further Planned Corrective Actions or Commitments in LER1999-08-25025 August 1999 Forwards LER 99-013-00,re RHR Heat Exchanger Bypass Valves Not Verified Per TS Surveillance.Surveillance Procedures Have Been Revised & There Are No Further Planned Corrective Actions or Commitments in LER ML20211M8191999-08-25025 August 1999 Confirms 990825 Telcon Between G Gilbert & R Carroll Re Mgt Meeting to Be Held on 990909 in Atlanta,Ga,To Allow Licensee to Present self-assessment of Catawba Nuclear Station Performance ML20211A9641999-08-20020 August 1999 Forwards SE Authorizing Licensee 990118 Request for Approval of Proposed Relief from Volumetric Exam Requirements of ASME B&PV Code,Section XI for Plant,Units 2 ML20211C1191999-08-18018 August 1999 Forwards ISI Rept Unit 1 Catawba 1999 RFO 11, Providing Results of ISI Effort Associated with End of Cycle 11 ML20211B9471999-08-18018 August 1999 Forwards Request for Relief 99-02,associated with Limited Exam Results for Welds Which Were Inspected During Unit 1 End of Cycle 11 RFO ML20211C3651999-08-17017 August 1999 Forwards Rev 25 to Catawba Nuclear Station Units 1 & 2 Pump & Valve Inservice Testing Program, Which Includes Reformatting of Manual & Addl Changes as Noted in Attached Summary of Changes ML20211F2971999-08-17017 August 1999 Forwards non-proprietary & Proprietary Updated Pages for DPC-NE-2009,submitted 980722.Pages Modify Fuel Design & thermal-hydraulic Analysis Sections of DPC-NE-2009. Proprietary Page 2-4 Withheld,Per 10CFR2.790 05000413/LER-1999-011, Forwards LER 99-011-00,re Missed Surveillance on Both Trains of CR Area Ventilation Sys Resulting in TS Violation.Planned Corrective Actions Stated in LER Represent Regulatory Commitment1999-08-16016 August 1999 Forwards LER 99-011-00,re Missed Surveillance on Both Trains of CR Area Ventilation Sys Resulting in TS Violation.Planned Corrective Actions Stated in LER Represent Regulatory Commitment ML20211B1121999-08-16016 August 1999 Forwards Topical Rept DPC-NE-2012, Dynamic Rod Worth Measurement Using Casmo/Simulate, Describing Results of Six Drwm Benchmark Cycles at Catawba & McGuire & Discusses Qualification to Use Drwm at Catawba & McGuire ML20210V0321999-08-13013 August 1999 Forwards Insp Repts 50-413/99-04 & 50-414/99-04 on 990606- 0717.Six Violations of NRC Requirements Identified & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20210S2751999-08-12012 August 1999 Forwards Monthly Operating Repts for July 1999 for Catawba Nuclear Station,Units 1 & 2.Revised Rept for June 1999,encl ML20210Q3751999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr as Listed,Thirty Days Before Exam Date,In Order to Register Individuals for Exam ML20210N9521999-08-0404 August 1999 Forwards Changes to Catawba Nuclear Station Selected Licensee Commitments Manual.Documents Constitutes Chapter 16 of Ufsar.With List of Effective Pages IR 05000413/19980131999-08-0202 August 1999 Discusses Integrated Insp Repts 50-413/98-13,50-414/98-13, 50-413/98-16,50-414/98-16 & NRC Special Repts 50/413/99-11 & 50-414/99-11 Conducted Between Aug 1998 & May 1999.Six Violations Occurred,Based on OI Investigation & Insp ML20210M6411999-07-29029 July 1999 Forwards Request for Relief 99-03 from Requirements of ASME Boiler & Pressure Vessel Code,In Order to Seek Relief from Performing Individual Valve Testing for Certain Valves in DG Starting Air (Vg) Sys 05000413/LER-1999-010, Forwards LER 99-010-01 Which Replaces LER 99-002.Rept Number Has Been Changed in Order to Conform to Numbering Convention Specified in NUREG-1022,since Primary Event Involved Both Units1999-07-22022 July 1999 Forwards LER 99-010-01 Which Replaces LER 99-002.Rept Number Has Been Changed in Order to Conform to Numbering Convention Specified in NUREG-1022,since Primary Event Involved Both Units IR 05000413/19990101999-07-22022 July 1999 Discusses Insp Rept 50-413/99-10 & 50-414/99-10 on 990314- 0424 & Forwards Notice of Violation Re Failure to Comply with TS 3.7.13,when Misalignment of Two Electrical Breakers Rendered SSS Inoperable from 981216-29 ML20217G5241999-07-20020 July 1999 Forwards Exam Repts 50-413/99-301 & 50-414/99-301 on 990524- 27,0603,07-10 & 16.Of Fourteen SRO & RO Applicants Who Received Written Exams & Operating Tests,Eight Applicants Passed & Six Failed Exam 05000413/LER-1999-009, Forwards LER 99-009-00,re Inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits.Root Cause & Corrective Actions Associated with Event Are Being Finalized & Will Be Provided in Supplement to Rept1999-07-19019 July 1999 Forwards LER 99-009-00,re Inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits.Root Cause & Corrective Actions Associated with Event Are Being Finalized & Will Be Provided in Supplement to Rept 05000414/LER-1999-001, Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Performed1999-07-15015 July 1999 Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Performed ML20209H4431999-07-14014 July 1999 Forwards Monthly Operating Repts for June 1999 for Catawba Nuclear Station,Units 1 & 2.Revised Rept for May 1999 on Unit Shutdowns Also Encl ML20210A5771999-07-14014 July 1999 Forwards Revsied Catawba Nuclear Station Selected Licensee Commitments Manual, Per 10CFR50.71(e),changing Sections 16.7-5,16.8-5,16.9-1,16.9-3,16.9-5 & 16.11-7.Manual Constitute Chapter 16 of UFSAR ML20216D3941999-07-14014 July 1999 Forwards Revs to Catawba Nuclear Station Selected Licensee Commitments Manual NUREG-1431, Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation1999-07-0909 July 1999 Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196L0371999-07-0808 July 1999 Approves Requested Schedule Change of Current two-year Requalification Examinations to non-outage dates.Two-year Cycle Will Start on 991001 & Will End on 020930 05000413/LER-1999-008, Forwards LER 99-008-00,re Operation Prohibited by TS 3.5.2. Rev to LER Will Be Submitted by 990812 Which Will Include All Required Info About Ventilation Sys Pressure Boundry Breach1999-07-0808 July 1999 Forwards LER 99-008-00,re Operation Prohibited by TS 3.5.2. Rev to LER Will Be Submitted by 990812 Which Will Include All Required Info About Ventilation Sys Pressure Boundry Breach ML20196J9001999-07-0606 July 1999 Informs That 990520 Submittal of Rept DPC-NE-3004-PA,Rev 1, Mass & Energy Release & Containment Response Methodology, Marked Proprietary Will Be Withheld Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 IR 05000413/19990031999-07-0101 July 1999 Discusses Insp Repts 50-413/99-03 & 50-414/99-03 Completed on 990605 & Transmitted by Ltr .Results of Delibrations for Violation Re Discovery of Potentially More Limiting Single Failure Affecting SGTS Analysis Provided 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217H0041999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML20217F1301999-10-0707 October 1999 Forwards Rev 1 to Request for Relief 99-03 from Requirements of ASME B&PV Code,In Order to Seek Relief from Performing Individual Valve Testing for Certain Valves in DG Starting (Vg) Sys 05000414/LER-1999-004, Forwards LER 99-004-01,providing Correction to Info Previously Provided in Rev 0 of Rept.Planned Corrective Actions Contain Commitments1999-09-27027 September 1999 Forwards LER 99-004-01,providing Correction to Info Previously Provided in Rev 0 of Rept.Planned Corrective Actions Contain Commitments 05000413/LER-1999-015, Forwards LER 99-015-00 Re Inoperability of Auxiliary Bldg Ventilation Sys That Exceeded TS Limits Due to Improperly Positioned Vortex Damper.Commitments Are Contained in Corrective Actions Section of Encl Rept1999-09-27027 September 1999 Forwards LER 99-015-00 Re Inoperability of Auxiliary Bldg Ventilation Sys That Exceeded TS Limits Due to Improperly Positioned Vortex Damper.Commitments Are Contained in Corrective Actions Section of Encl Rept 05000414/LER-1999-005, Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments1999-09-20020 September 1999 Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments ML20212D5321999-09-15015 September 1999 Informs That Duke Energy Corp Agrees to Restrict Max Fuel Rod Average Burnup to 60,000 Mwd/Mtu,In Order to Support NRC Final Approval & Issuance of Requested Amend ML20212B4641999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for Catawba Nuclear Station,Units 1 & 2 ML20212A5191999-09-0808 September 1999 Requests NRC Approval for Relief from Requirements of ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,App VI,VI-2430(c) & 2440(b).Approval of 99-GO-002 Is Requested by 000301 05000413/LER-1999-014, Forwards LER 99-014-00, Missed Surveillance & Operation Prohibited by TS Occurred as Result of Defective Procedures or Program & Inappropriate TS Requirements. Planned Corrective Action Stated in Rept Represents Commitment1999-09-0101 September 1999 Forwards LER 99-014-00, Missed Surveillance & Operation Prohibited by TS Occurred as Result of Defective Procedures or Program & Inappropriate TS Requirements. Planned Corrective Action Stated in Rept Represents Commitment 05000414/LER-1999-003, Forwards LER 99-003-01, Unplanned Actuation of ESFAS Due to a SG High Level Caused by Inadequate Procedural Guidance. Suppl Rept Provides Info Re Root Cause & Corrective Actions Associated with Event Developed Subsequent to Rev1999-08-31031 August 1999 Forwards LER 99-003-01, Unplanned Actuation of ESFAS Due to a SG High Level Caused by Inadequate Procedural Guidance. Suppl Rept Provides Info Re Root Cause & Corrective Actions Associated with Event Developed Subsequent to Rev 0 of LER ML20211H1741999-08-30030 August 1999 Forwards Comments on Catawba Nuclear Station Units 1 & 2 & McGuire Nuclear Station,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid.Ltr Dtd 990107,rept ATI-98-012-T005 & Partial marked-up Rept WCAP-14995 Encl ML20211M4451999-08-30030 August 1999 Forwards Summary of Util Conclusions Re Outstanding Compliance Issue Re Staff Interpretation of TS SR 3.0.1,per Insp Repts 50-369/99-03 & 50-370/99-03,as Discussed with NRC During 990618 Meeting 05000413/LER-1999-013, Forwards LER 99-013-00,re RHR Heat Exchanger Bypass Valves Not Verified Per TS Surveillance.Surveillance Procedures Have Been Revised & There Are No Further Planned Corrective Actions or Commitments in LER1999-08-25025 August 1999 Forwards LER 99-013-00,re RHR Heat Exchanger Bypass Valves Not Verified Per TS Surveillance.Surveillance Procedures Have Been Revised & There Are No Further Planned Corrective Actions or Commitments in LER ML20211B9471999-08-18018 August 1999 Forwards Request for Relief 99-02,associated with Limited Exam Results for Welds Which Were Inspected During Unit 1 End of Cycle 11 RFO ML20211C1191999-08-18018 August 1999 Forwards ISI Rept Unit 1 Catawba 1999 RFO 11, Providing Results of ISI Effort Associated with End of Cycle 11 ML20211C3651999-08-17017 August 1999 Forwards Rev 25 to Catawba Nuclear Station Units 1 & 2 Pump & Valve Inservice Testing Program, Which Includes Reformatting of Manual & Addl Changes as Noted in Attached Summary of Changes ML20211F2971999-08-17017 August 1999 Forwards non-proprietary & Proprietary Updated Pages for DPC-NE-2009,submitted 980722.Pages Modify Fuel Design & thermal-hydraulic Analysis Sections of DPC-NE-2009. Proprietary Page 2-4 Withheld,Per 10CFR2.790 05000413/LER-1999-011, Forwards LER 99-011-00,re Missed Surveillance on Both Trains of CR Area Ventilation Sys Resulting in TS Violation.Planned Corrective Actions Stated in LER Represent Regulatory Commitment1999-08-16016 August 1999 Forwards LER 99-011-00,re Missed Surveillance on Both Trains of CR Area Ventilation Sys Resulting in TS Violation.Planned Corrective Actions Stated in LER Represent Regulatory Commitment ML20211B1121999-08-16016 August 1999 Forwards Topical Rept DPC-NE-2012, Dynamic Rod Worth Measurement Using Casmo/Simulate, Describing Results of Six Drwm Benchmark Cycles at Catawba & McGuire & Discusses Qualification to Use Drwm at Catawba & McGuire ML20210S2751999-08-12012 August 1999 Forwards Monthly Operating Repts for July 1999 for Catawba Nuclear Station,Units 1 & 2.Revised Rept for June 1999,encl ML20210N9521999-08-0404 August 1999 Forwards Changes to Catawba Nuclear Station Selected Licensee Commitments Manual.Documents Constitutes Chapter 16 of Ufsar.With List of Effective Pages ML20210M6411999-07-29029 July 1999 Forwards Request for Relief 99-03 from Requirements of ASME Boiler & Pressure Vessel Code,In Order to Seek Relief from Performing Individual Valve Testing for Certain Valves in DG Starting Air (Vg) Sys 05000413/LER-1999-010, Forwards LER 99-010-01 Which Replaces LER 99-002.Rept Number Has Been Changed in Order to Conform to Numbering Convention Specified in NUREG-1022,since Primary Event Involved Both Units1999-07-22022 July 1999 Forwards LER 99-010-01 Which Replaces LER 99-002.Rept Number Has Been Changed in Order to Conform to Numbering Convention Specified in NUREG-1022,since Primary Event Involved Both Units 05000413/LER-1999-009, Forwards LER 99-009-00,re Inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits.Root Cause & Corrective Actions Associated with Event Are Being Finalized & Will Be Provided in Supplement to Rept1999-07-19019 July 1999 Forwards LER 99-009-00,re Inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits.Root Cause & Corrective Actions Associated with Event Are Being Finalized & Will Be Provided in Supplement to Rept 05000414/LER-1999-001, Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Performed1999-07-15015 July 1999 Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Performed ML20216D3941999-07-14014 July 1999 Forwards Revs to Catawba Nuclear Station Selected Licensee Commitments Manual ML20209H4431999-07-14014 July 1999 Forwards Monthly Operating Repts for June 1999 for Catawba Nuclear Station,Units 1 & 2.Revised Rept for May 1999 on Unit Shutdowns Also Encl ML20210A5771999-07-14014 July 1999 Forwards Revsied Catawba Nuclear Station Selected Licensee Commitments Manual, Per 10CFR50.71(e),changing Sections 16.7-5,16.8-5,16.9-1,16.9-3,16.9-5 & 16.11-7.Manual Constitute Chapter 16 of UFSAR 05000413/LER-1999-008, Forwards LER 99-008-00,re Operation Prohibited by TS 3.5.2. Rev to LER Will Be Submitted by 990812 Which Will Include All Required Info About Ventilation Sys Pressure Boundry Breach1999-07-0808 July 1999 Forwards LER 99-008-00,re Operation Prohibited by TS 3.5.2. Rev to LER Will Be Submitted by 990812 Which Will Include All Required Info About Ventilation Sys Pressure Boundry Breach ML20196G7461999-06-22022 June 1999 Requests Exemption from Requirements of 10CFR54.17(c) That Application for Renewed Operating License Not Be Submitted to NRC Earlier than 20 Yrs Before Expiration of Operating License Currently in Effect ML20196E9541999-06-18018 June 1999 Forwards SG Tube Insp Conducted During Unit 1 End of Cycle 11 Refueling Outage.Attachments 1,2,3 & 4 Identify Tubes with Imperfections in SGs A,B,C & D,Respectively ML20195K4571999-06-14014 June 1999 Forwards MORs for May 1999 & Revised MORs for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20195J1691999-06-10010 June 1999 Forwards Written Documentation of Background & Technical Info Supporting Catawba Unit 1,notice of Enforcement Discretion Request Re TS 3.5.2 (ECCS-Operating),TS 3.7.12 (Auxiliary Bldg Filtered Ventilation Exhaust Sys) ML20217G5771999-06-0909 June 1999 Forwards Post Exam Comments & Supporting Reference Matls for Written Exams Administered at Catawba Nuclear Station on 990603 05000414/LER-1999-002, Forwards Abstract of LER 99-002-00 Re Forced Shutdown of Plant as Result of Flow Restriction Caused by Corrosion of Afs Assured Suction Source Piping Due to Inadequate Testing. Final LER Will Be Submitted No Later than 9907081999-06-0303 June 1999 Forwards Abstract of LER 99-002-00 Re Forced Shutdown of Plant as Result of Flow Restriction Caused by Corrosion of Afs Assured Suction Source Piping Due to Inadequate Testing. Final LER Will Be Submitted No Later than 990708 ML20207F2381999-06-0101 June 1999 Forwards Copy of Catawba Nuclear Station Units 1 & 2 1998 10CFR50.59 Rept, for NRC Files ML20195J1131999-05-26026 May 1999 Requests Approval to Change Cycle Dates for Two Year Requalification Training Program Required by 10CFR55.59,to Improve Scheduling of Requalification Exams to non-outage Periods 05000413/LER-1999-007, Forwards LER 99-007-00,re Operation Prohibited by TS 3.4.7. Commitments Identified in LER Are Listed in Planned Corrective Actions Section1999-05-26026 May 1999 Forwards LER 99-007-00,re Operation Prohibited by TS 3.4.7. Commitments Identified in LER Are Listed in Planned Corrective Actions Section ML20195B4751999-05-24024 May 1999 Forwards Rev 7 to UFSAR Chapter 2 & Chapter 3 from 1998 UFSAR for Catawba Nuclear Station.List of Instructions on Insertion Encl ML20196L1851999-05-20020 May 1999 Forwards Proprietary & non-proprietary Version of Rev 1 to TR DPC-NE-3004, Mass & Energy Release & Containment Response Methodology, Consisting of Finer Nodalization of Ice Condenser Region.Proprietary Info Withheld ML20196L1791999-05-20020 May 1999 Communicates Util Licensing Position Re Inoperable Snubbers. Licensee Has Determined That Structure of ITS Has Resulted in Certain Confusion Re Treatment of Inoperable Snubbers 05000413/LER-1997-009, Forwards LER 97-009-02, Unanalyzed Postulated Single Failure Affecting SG Tube Rupture Analysis, Suppl Revises Planned C/A Described in Suppl 1 to Ler.Current Status of C/As & Addl C/As Planned,Provided in Rept1999-05-17017 May 1999 Forwards LER 97-009-02, Unanalyzed Postulated Single Failure Affecting SG Tube Rupture Analysis, Suppl Revises Planned C/A Described in Suppl 1 to Ler.Current Status of C/As & Addl C/As Planned,Provided in Rept ML20206T4481999-05-13013 May 1999 Forwards Rev 3 to Topical Rept DPC-NE-3002-A, UFSAR Chapter 15 Sys Transient Analysis Methodology, IAW Guidance Contained in NUREG-0390 ML20206R1721999-05-13013 May 1999 Forwards Monthly Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 & Revised Monthly Operating Repts for Mar 1999 ML20206T0281999-05-12012 May 1999 Forwards Changes to Catawba Nuclear Station Selected Licensee Commitments Manual. Document Constitutes Chapter 16 of UFSAR 05000413/LER-1999-006, Forwards LER 99-006-00,re CR Ventilation Sys Inoperability. Root Cause & Corrective Actions for Occurence Are Being Finalized & Will Be Reported in Supplement Rept on 9906071999-05-10010 May 1999 Forwards LER 99-006-00,re CR Ventilation Sys Inoperability. Root Cause & Corrective Actions for Occurence Are Being Finalized & Will Be Reported in Supplement Rept on 990607 ML20206N8201999-05-10010 May 1999 Forwards Revs 15 & 16 to Catawba Unit 1 Cycle 12 COLR, Per TS 5.6.5.Rev 15 Updates Limits for New Catawba 1 Cycle 12 Reload Core & Rev 16 Revises Values Re Min Boron Concentrations for Rwst,Cla & SFP ML20206J4431999-05-0303 May 1999 Forwards Changes to Catawba Nuclear Station Selected Licensee Commitments Manual, Per 10CFR50.71(e).Document Constitutes Chapter 16 of UFSAR ML20206D2141999-04-29029 April 1999 Forwards 1998 Annual Radioactive Effluent Release Rept for Catawba Nuclear Station,Units 1 & 2, Per Plant TS 5.6.3. Rept Contains Listed Documents ML20206E4101999-04-26026 April 1999 Forwards Four Copies of Rev 9 Todpc Nuclear Security & Contingency Plan,Per 10CFR50.54(p)(2).Changes Do Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR73.21 1999-09-08
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L5491990-09-14014 September 1990 Forwards Proprietary Response to Question Re Scope of Review of Topical Rept, Safety Analysis Physics Parameter & Multidimensional Reactor Transients Methodology, Per & 900723 Meeting.Response Withheld ML20059L5521990-09-14014 September 1990 Forwards Response to 18 Questions Re Topical Rept DPC-NE-2004,per NRC 900802 Request for Addl Info.Encl Withheld (Ref 10CFR2.790) ML20059K2021990-09-12012 September 1990 Submits Supplemental Response to Generic Ltr 89-14, Svc Water Sys Problems Affecting Safety-Related Equipment. Intake Structure Insp Program Developed.Procedures for Insp Implemented & Intake Structures Sampled & Analyzed ML20064A8041990-09-0505 September 1990 Notifies NRC of Mod to 890301 Response to Violations Noted in Insp Repts 50-413/86-18-01 & 50-414/86-18-01 Re Valves. All Valve Locking Mechanisms Would Be Installed by End of Unit 2 Refueling Outage (Approx Aug 1990) ML20064A5741990-09-0404 September 1990 Discusses Re Info to Support Util Position Relative to Resolving Issue of Main Steam Line Breaks Inside Ice Condenser Containments & Requests That Info Be Withheld (Ref 10CFR2.790) ML20059G3011990-09-0404 September 1990 Forwards Response to NRC 900327 Request for Addl Info Re BAW-10174, Mark-BW Reload LOCA Analysis for Catawba & Mcguire ML20059G8321990-08-30030 August 1990 Withdraws 880726 Proposed Tech Spec Change,Clarifying Tech Spec 3/4.7.6 Re Emergency Power Requirements for Control Room Ventilation Sys ML20059D2011990-08-27027 August 1990 Forwards Piedmont Municipal Power Agency , Authorizing Use of Annual Rept for NRC Docket Requirements ML20059D2441990-08-24024 August 1990 Forwards Special Rept PIR-1-C90-0261 on 900725 Re Cathodic Protection Sys Failure to Pass Acceptance Criteria of 60-day Surveillance.Std Work Request Generated to Check Voltage Potential at Test Station TS-36 on Weekly Basis ML20056B4981990-08-22022 August 1990 Responds to NRC Request for Addl Info Re General Relief Request for Pump Vibration Submitted 900315.Relief Request Changed to Insure Data Taken Over Range That Encompasses All Main Potential Noise Contributors ML20056B5011990-08-22022 August 1990 Responds to Violation Noted in Insp Repts 50-413/90-17 & 50-414/90-17.Corrective Actions:Review Will Be Conducted to Determine Category of Infrequently Run Procedures Needing Addl Verification Controls ML16259A2391990-08-22022 August 1990 Forwards Public Version of Rev 27 to Company Crisis Mgt Implementing Procedure CMIP-2, News Group Plan. W/ Dh Grimsley 900906 Release Memo ML20056B4971990-08-20020 August 1990 Clarifies Info Submitted in 871207 & s Re Steam Generator Tube Rupture Analysis Demonstration Runs. Demonstration Runs Met plant-specific Requirements in Section D to NRC SER on WCAP-10698 ML20059C1201990-08-20020 August 1990 Forwards Rept Summarizing Util Findings Re Three False Negative Blind Performance Urine Drug Screens Which Occurred During Jan & Feb 1990.Recommends That NRC Consider Generic Communication to Clearly State Reporting Requirement ML20059B6581990-08-17017 August 1990 Responds to Violation Noted in Insp Repts 50-413/90-15 & 50-414/90-15.Corrective Actions:Present Methods of Testing Operability of CO2 Fire Protection Sys Will Be Evaluated by 910201 to Determine If Addl Testing Necessary ML20059C1591990-08-17017 August 1990 Suppls by Providing Addl Info to Support Util Position Re Anl Confirmatory Analysis of Main Steamline Breaks in Ice Condenser Plants.Encl Withheld ML20063Q0951990-08-15015 August 1990 Forwards Monthly Operating Rept for Jul 1990 for Catawba Nuclear Station Units 1 & 2 & Revised Rept for June 1990 ML20059C1231990-08-15015 August 1990 Advises That Util Submitting Special Rept Re Valid Failure of Diesel Generator 2B Would Be Delayed Until 880229 Had Incorrect Ltr Date.Date of Ltr Should Have Been 880204 Instead of 880104.Corrected Ltr Encl ML20063Q2671990-08-14014 August 1990 Forwards Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 36 to CMIP-1,Rev 32 to CMIP-4,Rev 36 to CMIP-5,Rev 41 to CMIP-6,Rev 40 to CMIP-7,Rev 27 to CMIP-8 & Rev 35 to CMIP-9.W/DH Grimsley 900821 Release Memo ML20059C2211990-08-13013 August 1990 Forwards Revised Chapter 16, Selected Licensee Commitments Manual, to Plant Updated Fsar,Per 10CFR50.4 & 50.71.Manual Contains Commitments Which Require Control But Not Appropriate in Tech Specs ML20063Q0261990-08-10010 August 1990 Forwards Rev 0 to Catawba Unit 2 Cycle 4 Core Operating Limits Rept, Per Tech Spec 6.9.1.9 ML20063Q0671990-08-10010 August 1990 Submits Revised Response to Violations Noted in Insp Rept 50-413/90-09.Procedure to Verify Test Inputs Modified to Verify Dummy Input Signal to Channel RTD Circuit ML20058N0181990-08-0808 August 1990 Forwards Response to Request for Addl Info Re BAW-10174, Mark-BW Reload LOCA Analysis for Catawba & Mcguire ML20081E1601990-08-0101 August 1990 Advises of Completion of 900330 Commitment Re Standing Work Request for Insp of Air Flow Monitors & Dampers,Per Violations Noted in Insp Rept 50-413/90-03 & 50-414/90-03 ML20058P3261990-08-0101 August 1990 Forwards Public Version of Rev 26 to Station Directive 3.8.4, Onsite Emergency Organization ML20081E0951990-07-27027 July 1990 Forwards Decommissioning Financial Assurance Certification Rept for Duke Power Co,co-owner of Catawba Nuclear Station Units 1 & 2 ML20055H9741990-07-26026 July 1990 Forwards end-of-cycle 3 Steam Generator Insp Rept.Nineteen Tubes Removed from Svc by Plugging W/Rolled Mechanical Plug ML20055H5231990-07-24024 July 1990 Discusses co-licensee Relationship & Obligations Re Decommissioning Financial Assurance for Facilities ML20055H4571990-07-19019 July 1990 Responds to NRC Re Violations Noted in Insp Repts 50-413/90-11 & 50-414/90-11.Corrective actions:I-beams/ Hoists Rolled to Ends of Ice Condenser & Securely Located on Rails to Prevent Any Movement ML20055H1741990-07-18018 July 1990 Withdraws 880527 & 0725 Amends Clarifying Requirements for Containment Pressure Control Sys ML20055J3441990-07-17017 July 1990 Advises That Commitment Re Procedure IP/O/A/3190/01,per Violation in Insp Repts 50-413/90-06 & 50-414/90-06, Completed on 900619 ML20055H4131990-07-16016 July 1990 Forwards Public Version of Epips,Including RP/0/A/5000/07 & HP/0/B/1009/04 ML20055F8991990-07-13013 July 1990 Forwards Monthly Repts for June 1990 for Catawba Nuclear Station Units 1 & 2 & Operating Status Rept for May 1990 ML20055G2311990-07-13013 July 1990 Withdraws 880311 Proposed Amend to Tech Spec Table 3.3-3, Item 8.f Re Number of Instrumentation Channels Associated W/ Main Feedwater Pumps.Util Determined That Change Unnecessary ML20055F8461990-07-12012 July 1990 Requests 14-day Extension Until 900802 to Submit LER 414/90-010 to Investigate Power Supply Realignment ML20058P1231990-07-0707 July 1990 Advises That Commitment to Revise Maint Mgt Procedure 1.12 to Include Functional Verification Requirements & to Develop Retest Manual to Address Retest Requirements for Any Maint Performed on Components Completed on 900614 ML20055F4131990-07-0505 July 1990 Forwards Inservice Insp Rept Unit 1 Catawba 1990 Refueling Outage 4, Per 10CFR50.55(a)(q) & Tech Spec 4.0.5.Insp Performed Per Section XI of ASME Boiler & Pressure Vessel Code & Applicable Addenda ML20055D4291990-06-29029 June 1990 Supplemental Response to Violations Noted in Insp Repts 50-413/89-13 & 50-414/89-13,per .Personnel Responsible for Maintaining Crisis Mgt Ctr Drawing Trained. Util Will Continue to Evaluate Changes Made to Program ML20055E2191990-06-29029 June 1990 Submits Revised Commitment Dates Re Implementation of Dept Guidance on post-maint Testing,Per Commitment Made in 891002 Response to Violations in Insp Repts 50-413/89-19 & 50-414/89-19.Completion Date Changed to 900701 ML20044B0621990-06-26026 June 1990 Forwards Public Version of Revised EPIP HP/0/B/1009/05, Personnel/Vehicle Monitoring for Emergency Conditions. W/Dh Grimsley 900716 Release Memo ML20043H6921990-06-18018 June 1990 Advises of Revised Completion Date for VA Ductwork Cleaning to 901231,per Insp Repts 50-413/90-03 & 50-414/90-03. Vendor Personnel Assigned to Task Unavailable to Complete Cleaning Until Late 1990 Due to Outage Support Needs ML20043G1691990-06-15015 June 1990 Forwards Monthly Operating Repts for May 1990 for Catawba Nuclear Station,Units 1 & 2 & Corrected Monthly Operating Repts for Apr 1990 Re Personnel Exposure ML20055C8041990-06-15015 June 1990 Responds to NRC Re Violations Noted in Insp Repts 50-413/90-10 & 50-414/90-10.Corrective Actions:Instrument Root Valves Unisolated & Analog Channel Operational Tests for Low Temp Overpressure Protection Completed ML20043G4331990-06-13013 June 1990 Withdraws 900423 Proposed Amend to Tech Spec 4.6.1.8 Re Lab Test of Carbon Samples from Annulus Ventilation Sys ML20043G3771990-06-13013 June 1990 Withdraws 900423 Proposed Amend to Tech Spec 4.7.7 Which Required That Lab Test of Carbon Samples from Auxiliary Bldg Filtered Exhaust Sys Be Tested for Methyl Iodide Penetration of 0.71% ML20043G2511990-06-12012 June 1990 Withdraws 900419 Suppl to 871221 Application for Amends to Licenses NPF-35 & NPF-32 Re Tech Specs 4.7.6 Re Control Room Area Ventilation Surveillance Requirements ML20043G1741990-06-0707 June 1990 Responds to Request for Addl Info Re BAW-10174, Mark-BW Reload LOCA Analysis for Catawba & Mcguire. Correct RCS Operating Pressure Would Be 2,250 Psia as Identified in Table 3-1 ML20043G3451990-06-0707 June 1990 Forwards Proprietary Response to Request for Addl Info Re Topical Rept BAW-10174, Mark-BW Reload Safety Analysis for Catawba & Mcguire. Response Withheld ML20043G0721990-06-0707 June 1990 Responds to NRC 900510 Ltr Re Violations Noted in Insp Repts 50-413/90-09 & 50-414/90-09.Corrective Actions:Vc/Yc Train a Returned to Svc W/Supply Power from 2ETA.Terminal Box 1TB0X0346 Inspected & Insured Operable ML20043F6111990-06-0606 June 1990 Advises That Response to Request for Addl Info Re Operator Response Times During Simulated Steam Generator Tube Rupture at Facility,Will Be Delayed Until 900630 1990-09-05
[Table view] |
Text
.-
O
.9 DUKE POWER GOMPANY
. P.O. box 33180 CHARLOTTE, N.G. 28242
"^t.";.SI". "" c,Wo'7rge -
- . - - September 14, 1984
- Mr. Harold R. Denton, Director -
Office of Nuclear Reactor Regulation
. U. S. Nuclear Regulatory Commission Washington, D. C. 20555
. Attention: Ms. E. G. Adensam, Chief
. Licensing Branch No. 4
.. Re: Catawba' Nuclear Station Docket Nos.-50-413 and 50-414
Dear Mr. Denton:
On December 20,1983, Duke Power Company requested approval for application of 'the " leak-before-break" concept to Catawba Unit 2 to eliminate postulated
-_ pipe breaks in the Reactor Coolant System primary loop from the plant struc-tural design basis. Attachment 4 to that submittal provided a summary of
~
. estimated cost savings and operational benefits for elimination of primary loop pipe breaks on Catawba Unit 2._ Included in that summary was a projected occupational radiation ~ dose reduction of 600 man-rem. Attached is a copy of-the analysis which.was the basis of the dose . reduction estimate.
Very truly yours, Hal B. Tucker.
/{f(f
. ROS:slb Attachments
- cc: Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region II
- 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323
- NRC Resident Inspector Catawba Nuclear Station
- Mr.: Robert Guild, Esq.
Attorney-at-Law-P. O. Box 12097 Charleston, South Carolina . 29412 840924y*1884o914o'oo goaa N 6el !
- p 1 1
F -
~
1 Mr..' Harold R. ' Denton', Dir:ctor.
' Septemb:r 14,;.1984 -
Page Two' cc: :-Palmetto Alliance 21351 Devine Street
. Columbia,' South Carolina : 29205 Mr.~' Jesse L. Riley Carolina' Environmental Study Group 854 Henley- Place '
Charlotte, North Carolina 28207-r Y
s T
I
~
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-g.'d- - - 'WMh- %- -y,**-,,g-gg-e er-py9 gp9s,+4-'+-P--E'm P 'W 'sipe 6--e1M'-"*'TT^ e' F-**m-M8-'"T 7+4"-CS""W~M"4'*'-' 9vq' r<*P9*9-T'=T-W3"P
e ;+ '" :
. :,J * : .' .
November- 17,1983 MDPE-83-599 Memo to File
'~
Re: -Catawba Nuclear Station Removal of Rupture Restraints - Radiation Dose and Cost Estimate.
File No.: CN-1206.03-04, CN-1229.00 This analysis estimates the occupational radiation exposure and inherent cost associated with primary and non-primary loop rupture restraints.
~Atitached are three separate calculations involving: first, the dose assess-ment of twenty primary coolant loop rupture restraints; second, the cost savings associated with this occupational radiation exposure, and
. third,- the dose assessment and cost savings associated with 140 non-primary coolant loop restraints.
- The results of these calculations for a unit lifetime of 40 years are:
600 man-rem from 20 primary loop restraints and, 1.3 million dollars of radiation exposure cost.
-and 270 man-rem from 140 non-primary loop restraints and, 670 thousand. dollars of radiation exposure cost.
The cost estimates are based on the present value of money, that is, present staticn labor salaries. 0ccupational radiation exposure is based on expected average dose rates which may vary depending-on system operation.
However, the respective dollars per man-rem values of 2100 and 2500 compare-favorably to accepted Nuclear Production estimates of 2500 dollars per man-rem.
.This' assessment does 'not include-loss of time or access to other equipment,
, - loss of equipment laydown space, or other hazards associated with maintenance and inspection tasks due to pipe rupture restraints.
.R. G. Eble, Design Engineer I Mechanical & Nuclear Division
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Catawba - Occupational-Radiation Exposure Associated with Pipe Rupture Restraints
. Hypothesis: l Removal of main loop pipe rupture restraints inside containment at Catawba will eliminate-personnel radiation exposure related to restraint inspection tasks, restraint disassembly for pipe weld inspections and provide greater access and laydown space for other maintenance activities.
Assumptions:
Restraint assembly and disassembly' times are based on construction experience. Actual manpower will be higher due to protective clothing and access restrictions in high radiation areas.
-Radiation dose rates are assumed for normal expected shutdown conditions
. with no crud traps or " hot spots" near the work area.
- Manpower for a given task includes ' ingress and egress time to the work area.
Other-assumptions are included in the calculation portion of this analysis.
References:
J. E. Cherry: Duke Power Company, OA Department, Design Engineering Department on' inspection frequency and number of weld / restraint interferences.
Radiation Analysis Design Manual, Catawba Nuclear Station, Westinghouse, Dated 11-78.
NUREG/CR-0446, "Detennining Effectiveness of ALARA Design and Operational
- Features." 4 - NUREG-CR-3254, " Licensee Programs for Maintaining Occupational Exposure to
. Radiation As Low As Is Reasonably Achievable." 7-83
-H. J. Dameron, Duke Power Company, Nuclear Production Department, Technical Services, telephone. conversation on average wage of Nuclear Production Department employees.
6
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4 - . ,
r LCalculation:
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I.- Quality ' Assurance' inspection Criteria
_ , .statesithat primary piping ~. welds will be inspected at the 10-year
~
.," ~
/ outages. ' All mainiloop pipe restraints . considered in this analysis will
+ fimpact weld inspection time.and exposure. Each restraint will have to be
-partially. disassembled and then reassembled to perform the. inspection.
Manpower necessary .to remove / reinstall a restraint'has been estimated ,
Jto be: '
i 12 men ~, 21sl days' for maintenance labor and.4 men, 21s days for field' and .
-engineering support.
~ '
The dosei rate.'at shutdown near the primary. coolant piping is approximately 100 mR/Hr. General area dose rates in' lower containment-is approximately-30 mR/Hr.
It:is ' ass'umed that the maintenance labor is in the vicinity of the primary
. coolant piping.and the support labor;is maintained-in the general area.
The occupational exposure associated with the removal / reinstallation of-pipe; restraints for primary coolant weld inspection is:
" ~
.Maintena'nce Exposure = 40 man-hours x 0.1 Rem x 20 Restraints = 80 man-rem restraint Hr. ,
' Field Support Exposure' = 80 man-hours x 0.03 Rem x 20 Restraints;= 48 man-rem restraint- Hr !
N' i perl inspection frequency of 1 'every;10-year outage. -
.' Additional exposure.related to health physics personnel is' discussed in
~
1SectionLIII of this report.
3 =-
.II.. FAdditional occupationsi~ exposure'will be' received by Quality Assurance
, personnel ~during' inspection of pipe whip restraints. In discussion with
- " LQA personnel, pipe-restraints will be visually inspected approximately once every 5. years ~for proper. gap clearance. In the event of pipe / whip restraint-
. (crush' pad)' interaction a more detailed inspection of the restraint will be
~ performed. lit .is : assumed that i restraint undergoes detailed inspection .
L W' ;once every 10 years. Normal. visual . inspection takes 2 men is hour per
' restraint in a 100~mR/Hr radiation field with'no additional' field support.
Detailed inspe'c tion takes two men approximately 5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />s:near the primary. .
coolant.. piping with additional. 20 man-hours of field support in a general '
1 radiation field of.30 mR/Hr.. .-
~
The _ occupational radiation exposure associated with pipe whip restraint e : inspection is:
visual inspection:
~~';QA: exposure = 20 men ~x10.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> x 0.1 Rem x 20 Restraints = 2 man-rem
-insp freq .Hr inspec freg
~
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_ iins'pection frequency of once every 5 years.
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- Qhh I ~ Detailed Inspection
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r, JQA' exposure =: 2 men x '5.0- hours:x 0.1 Rem 'x 1 Restraint = 1.0 man-rem, insp freq- Hr insp freq l field support =14 men x15.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> x 0.03 Rem x 1 restraint = 0.6 man-rs=
insp freq Hr insp freq.
' inspection-frequency of once every 10 years.
III. Occupational " exposure; associated with health physics' personnel support
- Jincludes surveys, monitoring and normal HP support on the job. It is assumed that HP personnel .will spend the same number of manhours as maintenance an(Quality Assurance personnel .but will spend most of that y :timeJin the general, 30 mR/Hr, radiation field.
2 <
~ ~
For pipe. weld inspection, maintenance and -QA personnel HP support-
-radiation' exposure:
800 man-hours x 0.03 Rem = 24 man-rem ,
insp-freq Hr- insp freq inspection frequency of/once'every 10l years.
lFor pipe whip restraint inspection:
visual': .: 20 man-hours 'x 0.02. Rem = 0.6 man-rem -
V .insp freq inspection frequenc(of once every 5 years.
. - Detailed:
-10 man-hours.x .03 Rem /Hr; = 0.3 man'-rem-insp:freq _
inspection frequency of once every 10 years.
The total radiation dose associated with primary loop pipe whip restraints
_IV.-
n ~is:=
dos'e/insp: freq inspection frequency dose in plant' life Llabor group (man-rem) (insp/40 years) (man-rem) maintenance -~ 80 4 320
. weld 'fieldssupport 48 ~
4 192 einsp.' HP support 24- 4 96 608
_ ~
Quality! Assurance -2 8- 16
-- Restr ~ -Quality' Assurance -1 4- 4
- . insp field support' O.6~ 4 2.4 6 'HP; support. 0.6 8 4.8 m_ lHP support '
'0.3- 4 1.2 28
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? Total:-occupational exposure l associated with primary loop-pipe whip
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l restraints:is: 636 mari-rem
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i Catawba-Cost Savings Estimate for Radiation Exposure Associated with Primary Loop Rupture Restraints Hypothesis:
Removal of primary loop piping rupture restraints inside containment at Catawba will provide cost ~ savings associated with the ultimate reduction of radiation exposure. In the same way as exposure reduction, (see 9/14/83 correspondence), time spent in removing restraints for reactor coolant pipe. weld inspection, gap clearance inspection, and asso-ciated support of these tasks will be eliminated- thus saving employee time, protective clothing, radiation risk, and will provide the employee an opportunity to continue work in a radiation area.
- The cost of these activities will provide the basis for savings associated with the approximate 600 man-rem exposure savings per unit
. life.
TAssumptions:
Man-hours associated with each task and frequency of tasks from 9/14/83 correspondence used for dose reduction estimation.
Salaries for maintenance, health physics, QA/QC technician is $18/hr.
Supervision is $22/hr. Engineering support is $20/hr. and covers Duke Power employees only -- no contracted work.
No outage cost associated with pipe restraint maintenance or inspection activities .
Personnel access inside containment is allowed during system shutdown
-conditions only.-
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Calculation:
I.. Primary coolant pipe whip restraints 1.1. Cost associated with removal / reinstallation of restraints for weld inspections.
- Manpower
- . 40 man-hours per restraint per inspection frequency of once every 10 years.
. Radiation Dose: 40 man-hours x 0.1 Rem = 4 man-rem per restraint Hr per inspection frequency of once every 10 years.
' Cost: - A worker is allowed 1000 millirem per quarter (Duke. limit)-
and restraint work is assumed to take' place in one quarter
.of the year. Thus ~4 man-rem of radiation exposure will eliminate 4 employees from additional radiation work in the quarter. It is assumed that an employee restric'ted from work in a radiation area is worth 3/4 of his normal capacity to the company. A cost of 1/4 of the worker's salary is then associated with the inability to perform in a radiation area. Therefore the cost associated with '4 man-rem of maintenance personnel exposure is:
Cost = 4 man-rem x 520 hours0.00602 days <br />0.144 hours <br />8.597884e-4 weeks <br />1.9786e-4 months <br /> x $18 x 1 = $9360.'
1 man-rem quarter Hr T quarter per restraint per inspection frequency.
~
For all 20 restraints: cost.= $9360 x 20 = $187,000/insp freq.
and for 4 inspections in 40 years,
. Cost = $749,000 per unit lifetime.
All remaining calculations based on personnel exposure will
- follow this same. methodology in an abbreviated fonnat.
' I '. - -1.2 Field support 'of restraint remove / install for weld inspection:
-general labor 0 $18/hr + h engr 0 $20/hr = $19/hr.
Manpower: 4 men x 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> in general area (.03 Rem) restraint Hr.
per restraint per inspection.
H in one inspection: 20 restraints x 80 man-hours
= 1600 man-hours of support /I.F.
48 man-rem / inspection frequency.
,7--
t_
y,- =
e .
J: . * :
. Cost = :1600 man-hours x 0.03 Rem x 520 Hrs. x $19/Hr x 1 M" ?)Cs
,1 -1 man-rem quarter.
Hr quarter T
= ll5,000/ inspection frequency inspection: frequency 4 (in 40 yrs)
. Total cost: associated.with loss of field support personnel is:
115,000 x 4 = $460,000 per unit lifetime.
I. . 2. Inspection of pipe restraint gap clearance and detailed restraint
- inspection for pipe-restraint interaction.
2.1 ~ Visual inspection of all pipe restraints, no. field support.
Manpower: 2 men x 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> in pipe area (0.1 Rem) restraint Hr .
per inspection : frequency of 8 in 40 years.
for inspection frequency: 20-restraints x 1 man-hour =
20 man-hours every 5 years 20 man-hours x 0.1 Rem x 520 Hrs. x $18/hr x 1 = $4500/I.F.
1 man-rem Hr. quarter 4 quarter-
$4500 x 8'insp = $36,000 per unit lifetime.
40 years-
.2.2.1 Detailed inspection - maintenance manpower: 2 men x 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.= 10 man-hours /I.F. of 4 in 40 yrs, assuming 1/20 restraints undergoes detailed inspection /
every 10 years.
Cost = 10 man-hrs. x 0.1 Rem x 520 Hrs. x $18/Hr. x 1 = $2250/I.F..
1 man-rem Hr. qtr.
quarter inspection frequency of 1 in 10 years or 4 in 40 yrs.
Cost = 2250 x 4 = $9,000 per unit lifetime.
4 -
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,- 2. 2. 2. Detailed pipe restraint' inspection -~ field support in Lgeneral radiation -area.
f
. Manpower: 2 x. maintenance man-hours = 20. man-hours /I.F.
Rad.: Dose: 0.03 LRem xi20 man-hours = .6 man-rem.
.Hr.-
CostL= $19 x.1 x' .6 man-rem x 520 hrs.- = $1500/I . F. I .F.=4 in 7
. Hr: 4 .1-man-rem- qtr. -40 yrs.
l Cost"=_ $',500 x 4 =:$6000 per unit lifetime.
~
-I. 2 3L LCost associated with health physics support:
, ' Assume same manhours as maintenance and support personnel in a L general radiation: area of 0.03 Rem /Hr. This cost includes surveys, monitoring, badging, radiation work pennits and normal HP ' support on- the job.
3.l' Pihe inspection Ema'intenance and QA' health physics support- .
' Manpower ='800 man-hours Radiation Dose: '800 x .03. Rem /Hr. = 24 man-rem ,
Cost- $18 x:24 man-' rem x ~ 520 hours0.00602 days <br />0.144 hours <br />8.597884e-4 weeks <br />1.9786e-4 months <br /> x 1 = 56,000/I.F.
Hr 7 man-rem . otr 4_
quarter
~ '
Insp.~Freq. =~1Lin 10 years
- 3.2 ' Restraint Inspection .
13.2.1 V!sual inspection;cf all restraints
- Manpower: 20' man-hours /I.F.
- s. . Rad Dose: 20 x .03 Rem /Hr. = .6 man-rem
- Cost: $18 'x 1 x 6 man-rem x- 570 Hrs. = $1400/I.F. -
, H r.. T. :1 man-rem :qtr.
. quarter-I.F. '= l Lin 5 years.
_ 3.2.2.. Detailed inspection - maintenance + quality assurance HP
. support.
< Manpower: 10 man-hours
- Rad. Dose::10 x .03 Rem /Hr. = .3 man-rem iCost::$18 x'1lx .9 x 520 = $700/I.F.
Hr 4 T !
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I.F. = = 1 in 10 years. 2
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-I. - 4.- Other associated cost will include cost for protective clothing.
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Cost of protective clothing, i.e., material costs for throw-away objects and' processing,' cleaning and waste disposal is $13. per 1 change out. If we assume one change out every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (since most
! tasks'to be performed will extend to more than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) and assume
- radiation exposure limits will not be exceeded during this time
- period then the cost associated with protective clothing will be:
Total man-hours E man-hours /IF cost /IF from I. -1.1. - 3200 4/40 yrs- 800 2600 1.2. - 6400- '4/40 yrs. 1600 5200 2.1. - 160 8/40 yrs 20 65 2.2.1- 4/40 yrs 10 32.50 2.2.2 80 4/40 yrs 20- 65+
3.1 1600 4/40 yrs 40 130 3.2 1600 4/40 yrs 40 , 130 3.3 80 8/40 yrs 10 32.50
' 3.4 20 4/40 yrs 5 16.25 Total Cost : 13,200-x 1 change x $13 = $43,000.
4 man-hrs change
. I .- 5.--Total-cost associated'with 20 primary-loop pipe restriants based on radiation exposure:
cost - IF Total (in1000's) cI.l. 180,000 + 115,000 1 in 10 yrs 1180 I.2. 4500- 1 in 5 yrs 36
.+ 3750 1 in 10 yrs 15 I.3. ~56,000 + 700 1 in 10 yrs 63
+.1400 1 in 5 yrs- 11 I 4. 8200 1 in 10 yrs 33
+ 100 1 in 5 yrs 1 1,339,000 Total dose = 600 man-rem == $2200 man-rem
~
- all cost assumed to be in present value of money.
- assessment does.not include loss of time or access due to pipe
. restraints, loss of equipment laydown space or other hazards associated with maintenance and inspection tasks.
c
Occupational radiation exposure and cost estimate associated with non-primary coolant loop rupture restraints:
Assumptions:
1.. ' Restraints are smaller;.' easier to remove / install it is assumed to take ithe man-hours to remove / install. RC pipe restraints.
~
'2. 140 restraints evaluated in this cost savings estimate.
- 3. . dose rates will vary depending on location, background, and systems; weLwill: assume 25 mR/Hr. general area dose rates.
- 4. -assumptions used for RC pipe restraints will also apply.
Method:
.1. One in five restraints will' have to be removed / reinstalled for pipe
' inspection.with'an inspection frequency of once every ten years.
!21 All restraints will be visually inspected once every 5 years, one in twenty restraints will need further detailed inspection once every ten years.
- 3. Tasks.(1) and (2) above will need field support by Health Physics technicians, supervisors and engineering.
- 4. . Cost associated with anti-contamination clothing $13/4 man-hours.
Calculation:
- 1. . Cost associated with non-primary coolant piping restraints. Cost for
. restraint removal / installation for pipe-inspection':
l'.1 Maintenance -
Manpower: 1 x 140 restraints x 1 x 40 nian-hrs = 560 man-hours T E restraint insp freq
' Radiation dose: '.025 Rem x 560 man-hours = 14 man-rem /IF Hr IF Cost: $18 x 1 x 14 man-rem x 520 Hrs = $33,000/IF Hr. L 1 man-rem , qtr quarter
. Inspection frequency is once every 10 years Total Dose =-56 man-rem Total cost = $132,000 per unit lifetime
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-1.2 Field Support:
Manpower: .1 x 140 rest. x 80 man-hours x 1 = 1120 man hours F restraint 2 IF Radiation Dose: .025 Rem x 1120 man-hours = 23 man-rem Hr IF IF
-Cost: . $19 x 1 x 28 man-rem x 520' Hrs = $69.000/IF -
Hr 4' I man-rem qtr quarter.
Inspection frequency: _1 every 10 years.
Total Dose = 112 man-rem Total Cost = 276,000_ per unit lifetime.
- 2. Inspection of pipe restraint 2.1 ~ Visual . inspection of all-restraints once every 5 years', no field -
support.
Manpower: -140 restraints x .5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> x 2 men = 70 man-hours 2 restr IF Radiation Dose: .025 ' Rem x 70 man-hours = 1.75 man-rem Hr IF Cost: $18/hr x 1 x 1.75 man-rem x 520 Hrs = $4000/IF T- 1 man-rem . qtr quarter Inspection frequency: 1 in 5 years Total Radiation Dose = 14 man-rem
- Total Cost = '32,000 per unit lifetime 2.2 Detailed inspection of 1 in 20 restraint's- .
2.2.1 Maintenance tasks.
Manpower: 1 x 140 restraints x 10 man-hours = 35 man-hours 20 -2 IF Radiation Dose: .025. Rem x 35' man-hours = 1 man-rem Hr IF Cost: $18/hr x 1 x 1 nan-rem / quarter x. 520 hrs /qtr = $3200/1F 4 1 man-rem
- Total Dose = 1 man-rem x 40 yrs = 4 man-rem 10 yrs LT otal Cost = _ $2300 x 4 = $9200 per unit lifefime Inspection. Frequency: 1 in 10 year
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?2.2'.2I- Field support of ' detailed restraint -inspection, 2 times
. maintenance man-hours.
Manpower: 35 man-hours /IF_x 2 = 70 man-hours Radiation Dose: .025 Rem /Hr x 70 man-hours = 1.8 man-rem-
- 7 Cost
- ,$19/Hr x-l~.8 x 520 = $4000/IF IF = 1 in 10 yrs 4
^ Total Dose = 1.8 man-rem x 4 = 7.2 man-rem Total Cost = $4000'x 4 = $16,000 per unit lifetime
-3. -
Health Physics'and administrative support:
Assume same as maintenance and support in same radiation field.
This'. includes surveys, monitoring, badging, radiation work permits
- and normal I!P support.
3.~1 Pipe Inspection - maintenance and QA health physics su'pport Manpower: 560~ man-hours /IF Radiation Dose: 14 man-rem /IF
. Cost: .$33,000/IF-
.IF_=-1 in 10 yrs Total ~ Radiation Dose = 56 man-rem Total Cost = $132,000 per unit lifetime L3.2 Pipe: restraint Inspection.
3.2.1 Visual Inspection-Manpower: 70 man-hours /IF A Radiation Dose: 1.8 man-rem
- Cost: $4000/IF - IF = 1 in 5 yrs.
3.2.2- Detailed inspection maintenance support only Manpower: 35 man-hours /IF Radiation Dose: 0.9 man-rem /IF Cost: .$18/hr x 0.9 x 520 = $2100/IF 4
I IF '= 1 in 10 yrs.
Total Radiation Dose = 18 man-rem c Total Cost = $40,400 per ur.it lifetime n-e m--g ;w- g y, >+ p y-., 9m-'-gm<v ym -
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L4. . . Cost' associated wi .a personnel protection in.the work area, i .e. .. pro-tective clothing air pack,s, etc.
'$' N S- :- Assume ascin I.4:(that 1 change out occurs every 4 man-hours. .
.;' ~ _
manhours /IF-' E Cost, Clothing /IF-8 Fromillil.: 1680 1 in 10 yrs . $5460 J '2/i:
' ,?
~70 1 in 5 yrs $ 230
-2.2' 105- 1 in 10 yrs $ 340 i- '
' c 3.1 560 1 in 10 yrs $1820
'3.3.1 70 1 in 5 yrs $ 230 i
Q 3.3.21 35 1 in 10 yrs $ 115 D ~
d ~ Total. cost of protective clothing: $7735 every 10 yrs.
s
$ 460 every 5 yrs or.$30,940 + 3680 = $34,620 per unit lifetime. .
7 M "5. . Total cost associated.with non-primary coolant loop pipe restraints
- based on radiation exposure:
~
Rad Dose Tot- Cost Total
- 1. 56 + 112 , 168 132,000+276,000 = 408,000-
- 2. 14 '+ 4 + 7.2= 25 32,000+9200+16,000 = 57,000
- 13. 56 +\18 = 74 132,000+40,400'= 172,400
- 4. .
0 '34,600
' Totals 267 ~ $ 672,000 Total Radiation Dose = 267' man'-rem
,3 Total cost' savings = $672,000 per unit lifetime
. for 140 non-primary loop restraints or 2 man-rem and $4800 per non-7 -
. primary loop restrainty
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